ML20005A068
| ML20005A068 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/23/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| LSO5-81-06-080, LSO5-81-6-80, NUDOCS 8106290325 | |
| Download: ML20005A068 (5) | |
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Power & Light Conpany
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Dear Mr. Finfrock:
SUBJECT:
0YSTEP. CREEK - LIST AND STATUS OF SYSTEMATIC EVALUATION PROGRAM, PHASE II, GENERIC TOPICS By letter dated May 7,1981 (Letter to all SEP Licensees from G.C. Lainas), we sent you the list of generic topics that will be adifressed in the Systematic Evaluation Program integrated assessment (see Enclosure 3 of the letter).
The letter also stated that you would be informed by separate correspondence of the status of the generic topics and what further action, if any, is needed. of this letter presents the status of these generic topics and sup-ersedes Enclosurt 3 of the May 7, 1981 letter. The status code is. identical to that used in NUREG-0485 and, for convenience, is included herewith as Enclosure 2.
Topics in status code 2 require a response from tne licensee in order for topic review to continue. We need your response within three weeks of receipt of this letter in crder to meet our agreed upon schedules.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
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$p c June 23, 1981 Docket No. 50-219 _
LS05-81-06-080 Mr. I. R. Fi nf rock, J r.
Vice President - Jersey Central Power & Light Company Post Office Box 388 Forked River, New Jersey 08731 Dear Mr. Finfrock;
SUBJECT:
0YSTER CREEK - LIST AND STATUS OF SYSTEMATIC EVALUATION PROGRAM, PHASE II, GENERIC TOPICS By letter dated May 7,1981 (Letter to all SEP Licensees from G.C. Lainas), we sent you the list of generic topics that will be addressed in the Systematic Evaluation Program integrated assessment (see Enclosure 3 of the letter).
The letter also stated that you would be informed by separate correspondence of the status of the generic topics and what further action, if any, *is needed.
Enclosuit 1 of this letter presents the status of these generic topics and sup-ersedes Enclosure 3 of the May 7,1981 letter. The status code is identical to that used in NUREG-0485 and, fer convenience, is included herewith as Enclosure 2.
Topics in status code 2 require a response from the licensee in order for topic review to continue.
We need your response within three weeks of receipt of this letter in order to meet our agreed upon schedules.
Sincerely,
(
Vennis M. Crutch teld, lef Operating Reactors Bran n No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
ENCLOSURE 1 0YSTER CREEK GENERIC TASK STATUS TOPIC STATUS III-4.B - Turbine Missiles Status 0 This topic is not generic for Millstone 1.
It is being reviewed in the SEP on a plant specific basis.
III-7. A - Inservice Inspection -
Deleted - 11/16/79 Containments III-8.A - Loose Parts Monitoring Loose Parts Monitoring and Core Barrel Vibrat-Status 0 ion Monitoring (NRR Gene'Fic Activit No. B Loose Parts Monitoring Systens.
Implementation position has been developed in Revision 1 to Regulatory Guide 1.133 " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors." Letters will be sent to licensees requesting that a review be conducted and that a loose-parts detect-ion program be prepared and available for inspection 6 months after the effective is-suance date of the guide. Rev. I was is-l sued May 28,1981.)
Core Barrel Vibration Monitoring Status 0 (NRR Generic Activity No. C-12 Primary System Vibration Assessment.
Implementation position has not been developed.)
~ 1 BWR Jet Pumps Deleted - 11/16/79 Operating Indications o
.-6
OYSTER CREEK TOPIC' STATUS V Cog liance with Codes Inservice Inspection and Standards Status 3 - 02/05/81 (Multi-Plant issue A Inservice In-spection)
Inservice Testing Status 2 - Valves - 09/03/80 Status 2 - Pumps - 09/03/80 (Multi-Plant issue A Inservice Testing)
V Reactor Coolant Pump Deleted - 11/16/79 Overspeed VI Containment Leak Testing Status 4 - 06/04/81 (Multi-plant issue A Appendix J Leak Testing) -
VI-7.A.2 - Upper Plenum Injection Deleted - 11/16/79 VI-7. A.4 - Core Spray Nozzle Status 0 Effectiveness (Multi-Plant issue D Non-Jet Pump BWR Core Spray Perfo6 nance)
VI-7.D - Long Term Cooling Complete - 08/17/78 Passive Failures (Multi-Plant issue B-ll, Flood of Equip-ment Important to Safety, is not applic-able to this topic.)
VII-1.B - Trip Uncertainty and Complete - 08/17/78 Setpoint Analysis Review VII Frequency Decay Status 4 - 04/21/80 (NRR Generic Activity No. A-35.
Adequacy of offsite Power Systems. An analysis of frequency decay has been performed un-der subtask 8 of Task A-35.
An SER will be prepared that states t.here is no fre-qency decay condition of concern at this plant.)
VIII-1. A - Degraded Grid Voltage Status 3 - 08/11/80 (Multi-Plant issue B Degraded Grid Voltage)
ENCLOSURE 1
. OYSTER CREEK TOPIC STATUS IX Fire Protection Status 7 - 03/03/78 and 02/13/81 (Fire Protection SER)
Status 3 - 03/20/81 - (Safe Shutdown Cap-ability - Appendix R reviews)
(Multi-Plant Issue B-02 Fire Protection)
XI Appendix I Status 2 - 10/24/79 (Multi-Plant Issue A Appendix I -
Alara)
XI-2. - Radiological Monitoring Status 0
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Systens (NRR Generic Activity No. 8 Effluent and Process Monitoring.
Implementation Position has not developed for operating plants. A new Appendix A to Standard Re-view Plan 11.5 has been developed, which prescribes design and quality assurance criteria. )
XIII Safeguards / Industrial Complete.- 09/14/79 and 09/25/80 Security
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XVII - Operational QA Program Coaplete --08/17/78 I
ENCLOSURE 1 6
2 Et; CLOSURE 2 -
l KEY FOR STATUS COOES*
3 - ouESTION 11ESPONSE nECEIVED BY NRC 4 - OR AFT SE RECEIVED FROM REVIEW BRANCH 0 - TOPIC NOT STARTED 5 - OR AFT SE'SENT TO UTILITY 1 - OUESTIONS RECEIVED FROM REVIEW BRANCH 6 - SE RESPONSE RECEIVED BY NRC 2 - QUESTIONS SENT TO UTILITY 7 - TOPIC COMPLETE
- Date following a status Code in Enclosure 1 refers to either a letter from the NRC to Licensee or from the Licensee to NRC.
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